ML17252B191: Difference between revisions

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{{#Wiki_filter:Commonwe.Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR. /180-507 June 13, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s -Region III Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
* WN l 8 1980 Reportable Occurrence Report iJ 8Q..:.24/03L..:.Q-JI 050-249 , is being submitted to your office in acco:r;dance with Dresden Nuclear Power Station Technical Specification reactor protection system or engineered safety feature instrument settings which are found to be less conservative:::: than those established by the Technical Specifications but which do not vent the fulfillment of the functional requirements of.affected systems. BBS: B.B. Stephenson . Station Superintendent .presden Nuclear Power Station Enclosure cc: Director of Inspection & E.nfor.cement Director of Management Information & Program Control File/NRC 11.n1 ***--,. LICENSEE EVENT REPORT ?._. :*'C\J"TROL BLOCK: .___,._l_.....___.. _ _.1_!_...._-'J 0 !PLEASE PRINT OR TYPE'L REQUIREO lNFORMATIONI ro-rna I I I L I D IR Is I 3 IG)I 0 I 0 I -I 0 I 0 I O: I 0 I 0 1-. I 0 I 0 1(2)14 11 11 11 11 101 I I © 9 . LICENSEE. CODE,
* 14 . 15 LICENSE NUMBER 25 26 . LICENSE. TYPE JO. 57 CAT 5B J --** L.U©I 01 5 Io I o I o I 41 9 IGI o* 11 J 9_ 18 Io IG)I or 6 I 1 I o I 8 I o I G) 60 61 DOCKET NUMBER 08 69 EVENT DATE 74 75 . REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (iQ\ I During normal operation,* with reactor'-ievel instrument surveillance in progress, level ; 0 13 I I switch LIS 3-263-58B tripped at less than the* Tech. limit (Table 3.2.1) of 84 I 0 141. I inches. The safety significance of this event was minimal since channel "A" and the )a Is I I redundant Channel "B" instruments were operable. There was no effect on public health J 0 lo I I or safety. Previous occurrences.: R.O. 76-57/031-0,. Docket 50-237; 77....,51/031-0 and 80-23/031-0, Docket 50-249. 80. SYSTEM CODE I I IB I@ 9 10 G\ LEA/RO YEAR "V REPORT I 8 I 0 I NUMBER 21 . 22 ACTION . FUTURE TAKEN ACTION EFFECT ON PLANT CAUSE CAUSE COMP. VALVE CODE SUBCODE COMPONENT CODE SUBCODE
* SUSCODE 11IN1s1T IR 1u I@ L:J@} L:J@ 11 12 13 L=J 23 SHUTDOWN METHOD SEQUENTIAL* REPORT NO. I 0 I 2 I 4 I 24" 26. HOURS 18 OCCURRENCE CODE 1.......-1 10 13 27 28 29 19 20 REPORT TYPE 30 31 NPRD-4 FORM ::;us. PRIME COMP: SUPPLIER
* REVISION NO. 32 COMPONENT MANUFACTUR.E L:J@ L!J I o I o. I o ATTACHMENT SUBMITTED I Ll@ ll:l y 0 1 .o 33 34 . 35 36 3 7 40 41 42 43 44 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @ j 1 lo I I The cause of this event is.unknown at this time. The was immediately re-: , I 1 I : 1 I 2 I tested, with satisfactory results. Subsequent tests were performed, and each time the results were satisfactory. DIS* 500-2 will continue to* be done monthly. 47 I I :=IIIJ *---------------------------------------------------8 9 FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS . DISCOVERY DISCOVERY DESCRIPTION @ , Instrument Mechanic Surveillance so 1° 18 14 l@I NtA
* I L!J@I *a 9 10 12 45 ""46-* ACTIVITY CONTENT OF RELEASC: ..>.MOUNT OF ACTIVITY L2J@ N/A ' . I 8. 9 10 11 . 44 PERSONNEL EXPOSURES *(.;";;\ NUMBER DESCRIPTION m 1° 1° 1° 1021L:J 8 9 11 12 ?ERSONNEL INJURIES f,;:;\ N/A LOCATION*OF RELEASE @. 45 80 N/A NUMBER DESCRIPTIONa / 10 10 jO l@I NA a 9 11 LOSS OF OR DAMAGE TO FACILITY t4J\ TYPE. DESCRIPTION I v::::J zw* L:J@ . . N A 8 9 10 PUBLICITY f:::'\ ISSUEDf,;":;\ :IITJ* LJLl6 N A 8 9 10 . P. Holland 80 NRC USE ONLY *Q I "' I I I I I I I I I I I I 68 69 30.;; X-523 
}}

Revision as of 02:24, 26 April 2018

LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches
ML17252B191
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/13/1980
From: Stephenson B B
Commonwealth Edison Co
To: Keppler J G
NRC/RGN-III
References
BBS LTR. #80-507 LER 80-024/03L-0
Download: ML17252B191 (2)
v • d • e


Text

Commonwe.Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR. /180-507 June 13, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s -Region III Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

  • WN l 8 1980 Reportable Occurrence Report iJ 8Q..:.24/03L..:.Q-JI 050-249 , is being submitted to your office in acco:r;dance with Dresden Nuclear Power Station Technical Specification reactor protection system or engineered safety feature instrument settings which are found to be less conservative:::: than those established by the Technical Specifications but which do not vent the fulfillment of the functional requirements of.affected systems. BBS: B.B. Stephenson . Station Superintendent .presden Nuclear Power Station Enclosure cc: Director of Inspection & E.nfor.cement Director of Management Information & Program Control File/NRC 11.n1 ***--,. LICENSEE EVENT REPORT ?._. :*'C\J"TROL BLOCK: .___,._l_.....___.. _ _.1_!_...._-'J 0 !PLEASE PRINT OR TYPE'L REQUIREO lNFORMATIONI ro-rna I I I L I D IR Is I 3 IG)I 0 I 0 I -I 0 I 0 I O: I 0 I 0 1-. I 0 I 0 1(2)14 11 11 11 11 101 I I © 9 . LICENSEE. CODE,
  • 14 . 15 LICENSE NUMBER 25 26 . LICENSE. TYPE JO. 57 CAT 5B J --** L.U©I 01 5 Io I o I o I 41 9 IGI o* 11 J 9_ 18 Io IG)I or 6 I 1 I o I 8 I o I G) 60 61 DOCKET NUMBER 08 69 EVENT DATE 74 75 . REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (iQ\ I During normal operation,* with reactor'-ievel instrument surveillance in progress, level ; 0 13 I I switch LIS 3-263-58B tripped at less than the* Tech. limit (Table 3.2.1) of 84 I 0 141. I inches. The safety significance of this event was minimal since channel "A" and the )a Is I I redundant Channel "B" instruments were operable. There was no effect on public health J 0 lo I I or safety. Previous occurrences.: R.O. 76-57/031-0,. Docket 50-237; 77....,51/031-0 and 80-23/031-0, Docket 50-249. 80. SYSTEM CODE I I IB I@ 9 10 G\ LEA/RO YEAR "V REPORT I 8 I 0 I NUMBER 21 . 22 ACTION . FUTURE TAKEN ACTION EFFECT ON PLANT CAUSE CAUSE COMP. VALVE CODE SUBCODE COMPONENT CODE SUBCODE
  • SUSCODE 11IN1s1T IR 1u I@ L:J@} L:J@ 11 12 13 L=J 23 SHUTDOWN METHOD SEQUENTIAL* REPORT NO. I 0 I 2 I 4 I 24" 26. HOURS 18 OCCURRENCE CODE 1.......-1 10 13 27 28 29 19 20 REPORT TYPE 30 31 NPRD-4 FORM ::;us. PRIME COMP: SUPPLIER
  • REVISION NO. 32 COMPONENT MANUFACTUR.E L:J@ L!J I o I o. I o ATTACHMENT SUBMITTED I Ll@ ll:l y 0 1 .o 33 34 . 35 36 3 7 40 41 42 43 44 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @ j 1 lo I I The cause of this event is.unknown at this time. The was immediately re-: , I 1 I : 1 I 2 I tested, with satisfactory results. Subsequent tests were performed, and each time the results were satisfactory. DIS* 500-2 will continue to* be done monthly. 47 I I :=IIIJ *---------------------------------------------------8 9 FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS . DISCOVERY DISCOVERY DESCRIPTION @ , Instrument Mechanic Surveillance so 1° 18 14 l@I NtA
  • I L!J@I *a 9 10 12 45 ""46-* ACTIVITY CONTENT OF RELEASC: ..>.MOUNT OF ACTIVITY L2J@ N/A ' . I 8. 9 10 11 . 44 PERSONNEL EXPOSURES *(.;";;\ NUMBER DESCRIPTION m 1° 1° 1° 1021L:J 8 9 11 12 ?ERSONNEL INJURIES f,;:;\ N/A LOCATION*OF RELEASE @. 45 80 N/A NUMBER DESCRIPTIONa / 10 10 jO l@I NA a 9 11 LOSS OF OR DAMAGE TO FACILITY t4J\ TYPE. DESCRIPTION I v::::J zw* L:J@ . . N A 8 9 10 PUBLICITY f:::'\ ISSUEDf,;":;\ :IITJ* LJLl6 N A 8 9 10 . P. Holland 80 NRC USE ONLY *Q I "' I I I I I I I I I I I I 68 69 30.;; X-523
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